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2 edition of Neutronic and photonic studies of a fusion reactor blanket and shield found in the catalog.

Neutronic and photonic studies of a fusion reactor blanket and shield

Kenneth William Burn

Neutronic and photonic studies of a fusion reactor blanket and shield

with the objective of devizing an optimization procedure for several responses of interest.

by Kenneth William Burn

  • 75 Want to read
  • 2 Currently reading

Published by University of Birmingham in Birmingham .
Written in English


Edition Notes

Thesis (M.Sc.) - University of Birmingham, Dept of Physics, 1978.

ID Numbers
Open LibraryOL20661389M

cooled ceramic breeder blanket for the CFETR Xiaokang ZHANG, Songlin LIU, Xia LI et al.-Neutronic design studies of a conceptual DCLL fusion reactor for a DEMO and a commercial power plant I. Palermo, G. Veredas, J.M. Gómez-Ros et al.-Optimization process for the design of the DCLL blanket for the European DEMOnstration fusion reactor according toCited by: 1. The missions of CFETR are to generate about MW fusion power together with a 30%–50% envisioned burning time, and the major radius and minor radius are m and m respectively [].A ° torus sector of the CFETR was built up by MCNP based on an engineering design, including a blanket module at the inboard and one-and-a-half blanket modules at the outboard, as illustrated in Cited by: 1.

Aneutronic fusion is any form of fusion power in which the majority of the energy released is carried by charged particles. While the lowest-threshold nuclear fusion reactions release up to 80% of their energy in the form of neutrons, there also exist reactions in which the energy is released in the form of charged particles, typically protons or alpha particles. Successful aneutronic fusion would greatly reduce .   A preliminary design of fusion–fission hybrid energy reactor (FFHER) has been proposed by Institute of Nuclear Physics and Chemistry based on current fusion science and well-developed fission technology. In FFHER, shield blocks provide nuclear shielding and thermal shielding for internal and external blanket components. The hybrid of fusion core and fission blanket makes the spectra Cited by: 1.

Neutronic, Photonic, and Thermal Calculations Relevant To a Major Plasma Disruption Blanket Engineering in a Canister-Type Tokamak Blanket Ronald J. Onega, Bill M. Su Fusion Science and Technology / Volume 2 / Number 4 / October / Pages The blanket of a fusion reactor serves to absorb and transfer the energy of the fusion reaction products, and to produce the tritium necessary to refuel the reactor. This report outlines how these two functions are performed by lithium-bearing molten by:


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Neutronic and photonic studies of a fusion reactor blanket and shield by Kenneth William Burn Download PDF EPUB FB2

Neutronic research studies on fusion reactor blanket/shielding. Fusion reactor research activities on neutronic field in UTBLT are reviewed over the last ten years.

Experimental research works using a 14 MeV neutron source have been carried out in order to obtain good benchmark data for verification of the fusion reactor nuclear : T.

Iguchi, M. Nakazawa, Y. Oka, K. Furuta, S. Kondo. A detailed neutronic and photonic analysis of the `single box' design of the water-cooled Pb–17Li DEMO breeding blanket has been performed. Results obtained confirm the blanket tritium breeding self-sufficiency, even in the presence of 10 by: 8.

Within the European Fusion Technology Program, the Water-Cooled Lithium Lead (WCLL) DEMO breeding blanket line was selected in as one of the two EU lines to be developed in the next decade, in particular with the aim of manufacturing a Test Blanket Module Cited by: 3.

For optimization purposes, the initial specifications established over the simplified model have been refined on the detailed 3D design, modifying material and dimension of breeding blanket, shield and vacuum vessel in order to fulfil the priority requirements of a fusion reactor in terms of the fundamental neutronic responses.

Tritium breeding ratio, energy multiplication factor, radiation Cited by: 2. Fusion reactors operating on the deuterium (D-D) cycle are considered promising for their freedom from tritium breeding in the blanket. In this paper, neutronic and photonic calculations are undertaken covering several blanket models of the D-D fusion reactor, using presently available data, with a view to.

In order to achieve tritium self-sustaining and energy amplification of the magnetic confinement fusion reactors, sub-critical blanket and tritium breeding blanket were set around the plasma region. This work presents results of a parametric neutronic study for a DEMO-type reactor model based on the HCLL blanket with the objective to reduce the blanket radial thickness as much as possible without affecting the tritium breeding ratio (TBR) and assess the shielding performances with regard to the radiation loads to the super-conducting toroidal field coils at the inboard torus by: 8.

"Neutronic Analyses for CFETR With Modular Helium Cooled Lithium Ceramic Blanket." Proceedings of the 25th International Conference on Nuclear Engineering.

Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory by: 2.

Abstract: Neutronic assessment is the important foundation of Korean fusion demonstration reactor (K-DEMO) study. Previously, preliminary neutronic calculations using a simplified model have been performed, and optimized structure of blanket module and shield material has been by: 6.

practices (both cannot be realized without the other) for the neutronic design of the research reactor (RR) cores.

It completes the paper [1] and presents the general methodology of neutronic design studies for the safety and performance aspects and only slightly focuses on the reactivity shutdown systems and the neutronic calculation Size: KB.

¾sector MCNP power reactor model representing the modular structure of the blanket developed by FZK ¾Devised by integrating HCLL blanket module into the neutronic model of a DEMO-type reactor based on the parameters of PPCS model B ¾ MW fusion power assumed for the model ¾Proper simulation of the spatial distribution of the D-TFile Size: KB.

This paper describes the methodology developed to build the neutronic module, whose aim is to estimate main reactor neutronic parameters, i.e. tritium breeding ratio (TBR), multiplication factor (Me), nuclear heating and fast neutron flux as a function of the reactor main geometrical parameters (major radius, elongation, etc.), of the radial build, breeding blanket composition, blanket and shield thickness Cited by:   Position-dependent optimization calculations have been carried out on a D-D fusion reactor blanket/shield to maximize the energy gain in the blanket and to minimize the atomic displacement rate of the copper stabilizer in the superconducting magnet.

The results obtained by using the optimization code SWAN indicate (1) the advantage of D2O coolant over H2O coolant with respect Author: Tsuyoshi Shiba, Hideki Nakashima, Yukinori Kanda. Neutronic calculations were performed to optimize the SENRI blanket in terms of energy multiplication as well as tritium breeding ratio.

The blanket employs a thick (∼ cm) Li layer as breeder/ by: 3. This work summarizes the results of a neutronic study on the HCLL blanket for a DEMO-type fusion reactor. The analysis is based on three-dimensional Monte Carlo calculations using the MCNP-4C code.

the blanket and shield. The aim of the present study is to analyze the relation between the neutron source ratio and the nuclear characteristics of D-D fusion reactor blankets and shields, by examining the behavior of D-D and D-T source neutrons in both blanket and shield.

Chapter II pre. In this study, the neutronic performance of the ARIES-RS fusion reactor design using different types of thorium fuels, namely ThO2 or ThN dispersed in graphite or BeO, was investigated.

In this paper, neutronic and photonic calculations are undertaken covering several blanket models of the D-D fusion reactor, using presently available data, with a view to comparing the nuclear.

The photon interaction cross sections are flat weighted. A P 3 group coupled neutron and gamma-ray cross section library for neutronic studies in fusion reactor blankets or shield for 28 elements. [ top ]. Nuclear performance analyses of the HCLL breeder blanket for a fusion power reactor Article in Fusion Engineering and Design 84(2) June with 36 Reads How we measure 'reads'.

Neutronic Activation Analysis for ITER Fusion Reactor Barbara Caiffi ° Congresso Nazionale SIF. 2 Outlook BLANKET VACUUM VESSEL DIVERTOR POLOIDAL FIELD COILS TOROIDAL FIELD COILS 28 m. 16 28 m 30 m ITER Machine Official Model for ITER neutronic analysis Represents 40°sector of the reactor.

During the operations of the next experimental fusion machine three breeding test blanket modules (TBM) for a power reactor will be inserted in the horizontal ports and their performance examined. The insertion will change the overall shielding capability of the structure and thus the regular operability of the machine could be affected.

In this paper, I report the Monte Carlo simulations made.2 Study of the tritium production in a 1-D blanket model with Monte Carlo methods Objectives Collapse the blanket model in one dimension. Obtain the neutronic uxes through a blanket so they will be able to be integrated to the AINA code.

Obtain the TBR of a blanket. Obtain other data as neutronic energy deposition, photon.